Materials Library
UO2 (3% enriched)
FuelsUO₂
Uranium dioxide at 3 wt% U-235 enrichment. Standard fuel for commercial PWRs and BWRs. This is the compendium's own UO₂ entry, whose uranium is 3.0 wt% enriched.
ρ = 10.96 g/cm³ · PNNL-15870
UO2 (4.5% enriched)
FuelsUO₂
Uranium dioxide at 4.5 wt% U-235 enrichment. Common in high-burnup PWR fuel assemblies.
ρ = 10.96 g/cm³ · derived recipe
UO2 (5% enriched)
FuelsUO₂
Uranium dioxide at 5 wt% U-235 enrichment. The licensing ceiling for standard commercial fuel in the United States.
ρ = 10.96 g/cm³ · derived recipe
UO2 (19.75% HALEU)
FuelsUO₂
Uranium dioxide at 19.75 wt% U-235 — high-assay low-enriched uranium, the working fuel of most advanced reactor and research reactor designs.
ρ = 10.96 g/cm³ · derived recipe
MOX (mixed oxide, ~5% Pu)
Fuels(U,Pu)O₂
Mixed-oxide fuel: reactor-grade plutonium in a depleted-uranium matrix (0.25 wt% U-235). Plutonium is 4.7 wt% of the heavy metal.
ρ = 11 g/cm³ · PNNL-15870
Uranium Nitride
FuelsUN
Uranium mononitride at 3 wt% U-235. High uranium density and high thermal conductivity make it attractive for advanced and space reactors.
ρ = 14.31 g/cm³ · PNNL-15870
Uranium Carbide
FuelsUC
Uranium monocarbide at 3 wt% U-235. High heavy-metal density and good thermal properties for fast and space reactor fuel.
ρ = 13.63 g/cm³ · PNNL-15870
UZrH₁.₆ (TRIGA fuel)
FuelsUZrH₁.₆
Uranium–zirconium hydride fuel used in TRIGA research reactors. The hydride matrix is what gives TRIGA its large prompt negative temperature coefficient.
ρ = 5.97 g/cm³ · derived recipe
Zircaloy-2
Cladding & StructuralZirconium alloy cladding used in BWRs. Low absorption cross section with good corrosion resistance.
ρ = 6.56 g/cm³ · PNNL-15870
Zircaloy-4
Cladding & StructuralZirconium alloy cladding used in PWRs. No nickel, which improves hydrogen pickup resistance in PWR coolant chemistry.
ρ = 6.56 g/cm³ · PNNL-15870
Stainless Steel 304
Cladding & StructuralAustenitic stainless steel used for reactor structural components, piping, and vessel internals.
ρ = 8.03 g/cm³ · PNNL-15870
Stainless Steel 316
Cladding & StructuralMolybdenum-bearing austenitic stainless steel with improved corrosion resistance. Used in fast reactor cladding, PWR internals, and hot-leg piping.
ρ = 8 g/cm³ · PNNL-15870
Inconel 718
Cladding & StructuralNickel–chromium superalloy used in vessel head penetrations, springs, and high-temperature structure.
ρ = 8.19 g/cm³ · PNNL-15870
Hastelloy-N
Cladding & StructuralNickel–molybdenum alloy developed for molten-salt service. The structural material of the MSRE and of most proposed MSR designs.
ρ = 8.86 g/cm³ · derived recipe
Carbon Steel (AISI 1045)
Cladding & StructuralPlain medium-carbon steel, for structural supports, containment liner, and shielding geometry where the exact alloy does not matter.
ρ = 7.872 g/cm³ · PNNL-15870
Light Water
Moderators & CoolantsH₂O
Room-temperature light water — moderator and coolant in PWRs and BWRs.
ρ = 0.997 g/cm³ · PNNL-15870
Heavy Water
Moderators & CoolantsD₂O
Deuterium oxide at room temperature — moderator and coolant in CANDU and other heavy-water reactors, where the neutron economy allows natural-uranium fuel.
ρ = 1.1044 g/cm³ · PNNL-15870
Graphite
Moderators & CoolantsC
Nuclear-grade graphite moderator, for gas-cooled reactors (AGR, HTGR), RBMK, and molten-salt designs.
ρ = 1.7 g/cm³ · PNNL-15870
Beryllium
Moderators & CoolantsBe
Beryllium metal reflector and moderator for research and test reactors. Excellent neutron economy, and Be-9(n,2n) makes it a multiplier as well as a reflector.
ρ = 1.848 g/cm³ · PNNL-15870
Beryllium Oxide
Moderators & CoolantsBeO
Beryllia moderator and reflector for compact reactors. Denser than graphite with excellent thermal conductivity.
ρ = 3.01 g/cm³ · PNNL-15870
FLiBe
Moderators & CoolantsLi₂BeF₄
Lithium fluoride–beryllium fluoride molten salt, the coolant and fuel carrier of fluoride-salt-cooled and molten-salt reactors.
ρ = 1.94 g/cm³ · derived recipe
FLiNaK
Moderators & CoolantsLiF-NaF-KF
Lithium–sodium–potassium fluoride eutectic, used as a secondary coolant and heat-transfer salt in molten-salt designs.
ρ = 2.09 g/cm³ · derived recipe
Sodium
Moderators & CoolantsNa
Sodium coolant for sodium-cooled fast reactors — EBR-II, BN-600/800, Natrium.
ρ = 0.971 g/cm³ · PNNL-15870
Lead
Moderators & CoolantsPb
Natural lead coolant for lead-cooled fast reactors, and a workhorse gamma shield.
ρ = 11.35 g/cm³ · PNNL-15870
Lead-Bismuth Eutectic
Moderators & CoolantsPb-Bi
Lead–bismuth eutectic: a liquid-metal coolant for fast reactors and spallation targets, melting at about 125 °C instead of lead's 327 °C.
ρ = 10.17 g/cm³ · derived recipe
Carbon Dioxide
Moderators & CoolantsCO₂
Carbon dioxide at room conditions — coolant in Magnox and AGR reactors, and the working fluid of supercritical CO₂ power cycles.
ρ = 0.00184212 g/cm³ · PNNL-15870
Helium
Moderators & CoolantsHe
Helium at room conditions — HTGR and VHTR coolant, and the fill gas in a fuel-cladding gap.
ρ = 0.000166322 g/cm³ · PNNL-15870
Ordinary Concrete (Portland)
ShieldingPortland cement concrete — the primary biological shield in most reactor facilities.
ρ = 2.3 g/cm³ · PNNL-15870
Baryte Concrete
ShieldingHigh-density concrete with baryte (BaSO₄) aggregate, for gamma shielding where thickness is limited.
ρ = 3.35 g/cm³ · PNNL-15870
Borated Polyethylene (10% B)
Shielding(CH₂)ₙ + B
Polyethylene loaded with 10 wt% natural boron: hydrogen slows the neutrons down and B-10 absorbs them, in one material.
ρ = 1 g/cm³ · PNNL-15870
Polyethylene
Shielding(CH₂)ₙ
High-density polyethylene — the densest practical hydrogen source, and so an efficient neutron shield per centimetre.
ρ = 0.93 g/cm³ · PNNL-15870
B₄C (natural boron)
AbsorbersB₄C
Boron carbide with natural boron (19.9 at% B-10) — control rod and shutdown absorber, and the most common burnable absorber outside the fuel.
ρ = 2.52 g/cm³ · PNNL-15870
B₄C (90% B-10 enriched)
AbsorbersB₄C
Boron carbide enriched to 90 at% B-10, for control rods and shields that need maximum absorption per unit volume.
ρ = 2.393 g/cm³ · derived recipe
Ag-In-Cd Control Rod
AbsorbersAg-In-Cd
Silver–indium–cadmium alloy, the standard PWR control rod absorber. Absorbs across a wide energy range instead of relying on one resonance.
ρ = 10.17 g/cm³ · derived recipe
Gadolinium Oxide
AbsorbersGd₂O₃
Gadolinia burnable absorber, usually mixed into UO₂ pellets at a few weight percent. Gd-155 and Gd-157 have the largest thermal capture cross sections of any stable nuclides.
ρ = 7.41 g/cm³ · derived recipe
Hafnium
AbsorbersHf
Hafnium metal control rod absorber. Used where a rod has to last: successive captures walk through the isotope chain and every step still absorbs.
ρ = 13.31 g/cm³ · derived recipe
Europium Oxide
AbsorbersEu₂O₃
Europia control and burnable absorber material, used in Russian reactor designs and in research reactor control elements.
ρ = 7.42 g/cm³ · derived recipe
Dry Air
Gases & OtherDry air near sea level, for streaming paths, room modelling, and atmospheric transport.
ρ = 0.001205 g/cm³ · PNNL-15870
Argon
Gases & OtherAr
Argon at room conditions — cover gas above sodium in an SFR, where it keeps air away from the coolant.
ρ = 0.00166201 g/cm³ · PNNL-15870
Nitrogen
Gases & OtherN₂
Nitrogen at room conditions, for inerting containment and fuel handling areas.
ρ = 0.00116528 g/cm³ · PNNL-15870
Void / Vacuum
Gases & OtherVacuum or void region: no material, and particles stream through without interacting.
no material